Author: E. MizzanPublisher: Chalk River, Ont. : Fuel Engineering Branch, Chalk River Nuclear Laboratories
ISBN:
Category :
Languages : en
Pages : 17
Book Description
Facilities for Post-irradiation Examination of Experimental Fuel Elements at Chalk River Nuclear Laboratories
Author: E. MizzanPublisher: Chalk River, Ont. : Fuel Engineering Branch, Chalk River Nuclear Laboratories
ISBN:
Category :
Languages : en
Pages : 17
Book Description
FACILITIES FOR POST-IRRADIATION EXAMINATION OF EXPERIMENTAL FUEL ELEMENTS AT CHALK RIVER NUCLEAR LABORATORIES.
Author: Atomic Energy of Canada LimitedPublisher:
ISBN:
Category :
Languages : en
Pages : 39
Book Description
Canada Enters the Nuclear Age
Author: Atomic Energy of Canada LimitedPublisher: McGill-Queen's Press - MQUP
ISBN: 9780773516014
Category : Business & Economics
Languages : en
Pages : 466
Book Description
The nuclear energy company has overseen the production of its own history, focusing on programs at its laboratories in Chalk River, Ontario, and Whiteshell, Manitoba between 1943 and 1985. The 16 scientists who wrote the narrative discuss the organization and operations of the laboratories, nuclear safety and radiation protection, radioisotopes, basic research, developing the CANDU reactor, managing the radioactive wastes, business development, and revenue generation. Canadian card order number: C97-900188-9. Annotation copyrighted by Book News, Inc., Portland, OR
Post-irradiation Examination
Author: Publisher: Thomas Telford Publishing
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 380
Book Description
The Dynamic Analysis Facility at the Chalk River Nuclear Laboratories
Author: Argue, D. SPublisher: Chalk River, Ont. : Chalk River Nuclear Laboratories
ISBN:
Category :
Languages : en
Pages : 56
Book Description
Construction of a Post-Irradiated Fuel Examination Shielded Enclosure Facility
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The U.S. Department of Energy (DOE) has committed to provide funding to the Idaho National Laboratory (INL) for new post-irradiation examination (PIE) equipment in support of advanced fuels development. This equipment will allow researchers at the INL to accurately characterize the behavior of experimental test fuels after they are removed from an experimental reactor also located at the INL. The accurate and detailed characterization of the fuel from the reactor, when used in conjunction with computer modeling, will allow DOE to more quickly understand the behavior of the fuel and to guide further development activities consistent with the missions of the INL and DOE. Due to the highly radioactive nature of the specimen samples that will be prepared and analyzed by the PIE equipment, shielded enclosures are required. The shielded cells will be located in the existing Analytical Laboratory (AL) basement (Rooms B-50 and B-51) at the INL Material and Fuels Complex (MFC). AL Rooms B-50 and B-51 will be modified to establish an area where sample containment and shielding will be provided for the analysis of radioactive fuels and materials while providing adequate protection for personnel and the environment. The area is comprised of three separate shielded cells for PIE instrumentation. Each cell contains an atmosphere interface enclosure (AIE) for contamination containment. The shielding will provide a work area consistent with the as-low-as-reasonably-achievable (ALARA) concept, assuming a source term of 10 samples in each of the three shielded areas. Source strength is assumed to be a maximum of 3 Ci at 0.75 MeV gamma for each sample. Each instrument listed below will be installed in an individual shielded enclosure: Shielded electron probe micro-analyzer (EPMA) Focused ion beam instrument (FIB) Micro-scale x-ray diffractometer (MXRD). The project is designed and expected to be built incrementally as funds are allocated. The initial phase will be to fund the construction activities, which will include facility modifications and construction of one shielded enclosure. Follow-up activities will be to construct two additional shielded enclosures to complete the suite of three separate but connected remote operated examination areas. Equipment purchases are to be capital procurement spread out over several years on a funded schedule. This paper discusses safety and operational considerations given during the conceptual design phase of the project. The paper considers such things as project material at risk (MAR), new processes and equipment, potential hazards, and the major modification evaluation process to determine if a preliminary Documented Safety Analysis (PDSA) is required. As part of that process, an evaluation was made of the potential hazards with the new project compared to the existing and historical work and associated hazards in the affected facility.
An International Spent Nuclear Fuel Storage Facility
Author: Russian Academy of SciencesPublisher: National Academies Press
ISBN: 0309181186
Category : Science
Languages : en
Pages : 302
Book Description
As part of a long-standing collaboration on nuclear nonproliferation, the National Academy of Sciences and the Russian Academy of Sciences held a joint workshop in Moscow in 2003 on the scientific aspects of an international radioactive disposal site in Russia. The passage of Russian laws permitting the importation and storage of high-level radioactive material (primarily spent nuclear fuel from reactors) has engendered interest from a number of foreign governments, including the U.S., in exploring the possibility of transferring material to Russia on a temporary or permanent basis. The workshop focused on the environmental aspects of the general location and characteristics of a possible storage site, transportation to and within the site, containers for transportation and storage, inventory and accountability, audits and inspections, and handling technologies.
Energy Research Abstracts
Author: Preliminary assessment of bedrock disposal of low- and intermediate-level radioactive waste at the Chalk River Laboratories site : summary report
Author: J. TorokPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
The btf-105 experiment in the blowdown test facility is one of a series of experiments sponsored by the candu owners group (cog) to determine the release, transport and deposition of fission products from nuclear fuel under high-temperature transient conditions. the btf-105 experiment has been broken up into two tests: btf-105a and btf-105b. the btf-105a test is a precursor to the btf-105b test, which will generate fission product release data used to benchmark candu safety analysis codes. the btf-105a test will be used to assess instrumentation and procedures to be used during btf-105b, and to generate correlations between fuel sheath and fuel centreline temperatures. fission product release and transport data will also be obtained from low burnup fuel. the btf-105a test consists of a fuel stringer containing a single unirradiated instrumented zircaloy-clad uo2 fuel element. the assembly will be irradiated at a linear power of 50 kw/m for 10 days to establish an inventory of fission products in the fuel. following the soak irradiation, the stringer will be subjected to a coolant blowdown where the volume average temperature of the uo2 will rise to and be maintained at about 1600-1800 degrees c for about 10 minutes. the fuel element is predicted to fail during the ramp up to this temperature due to complete oxidation of the sheath. fission products released during the transient will be monitored by gamma spectrometers. following the test, the fuel stringer will be removed from the reactor and destructively examined in the crl hot cells. grab samples from inside the test section will also be removed and analyzed for fission products. this report presents an overall plan for the activities to be completed before, during and after the btf-105a blowdown test.
Author: